Abstract: A method and device for limiting the degassing of tritiated waste issued from the nuclear industry are provided. The method reduces an amount of generated tritiated hydrogen (T2 or HT) and/or tritiated water (HTO or T2O) including at least one piece of tritiated waste from the nuclear industry. The method includes placing the package in contact with a mixture including manganese dioxide (MnO2) combined with a component that includes silver; and placing the package in contact with a molecular sieve.

Abstract: A method and device for limiting the degassing of tritiated waste issued from the nuclear industry are provided. The method reduces an amount of generated tritiated hydrogen (T2 or HT) and/or tritiated water (HTO or T2O) including at least one piece of tritiated waste from the nuclear industry. The method includes placing the package in contact with a mixture including manganese dioxide (MnO2) combined with a component that includes silver; and placing the package in contact with a molecular sieve.

Abstract: An apparatus for recovery of tritium from contaminated gaseous mixtures by way of isotope-exchange processes includes a container having a preferably cylindrical shape made of steel or other suitable metal or glass, referred to as “module” (1), which contains at least one permeator tube (T) made of metal or metal alloy selectively permeable to hydrogen and its isotopes, wherein the tube (T) is set in cantilever fashion with its free end closed, there being further provided elements for applying an axial tensile force on the free end of the permeator tube (T) and elements for electrical connection of the free end of the tube (T) to an end flange (FF) of the module (1) adjacent thereto.

Abstract: A process for removal of tritium from materials that are contaminated thereby envisages the use of a detritiation reactor RT, in which the reaction for the removal of tritium from the waste takes place, the waste being recovered by a flow of moist inert gas in which an extremely low percentage of humidity is used. The heated waste releases a current of tritiated gases, the current of gases being removed from the reactor via the moist inert gas, which conveys it into a membrane reactor RM for decontamination. The membrane reactor, in fact, is able to remove selectively the tritium present in the mixture of gases: there is thus the dual advantage of purifying the mixture of gases and of recovering the tritium contained therein.

Abstract: A process for removal of tritium from materials that are contaminated thereby envisages the use of a detritiation reactor RT, in which the reaction for the removal of tritium from the waste takes place, the waste being recovered by a flow of moist inert gas in which an extremely low percentage of humidity is used. The heated waste releases a current of tritiated gases, the current of gases being removed from the reactor via the moist inert gas, which conveys it into a membrane reactor RM for decontamination. The membrane reactor, in fact, is able to remove selectively the tritium present in the mixture of gases: there is thus the dual advantage of purifying the mixture of gases and of recovering the tritium contained therein.

Abstract: An apparatus for recovery of tritium from contaminated gaseous mixtures by way of isotope-exchange processes includes a container having a preferably cylindrical shape made of steel or other suitable metal or glass, referred to as “module” (1), which contains at least one permeator tube (T) made of metal or metal alloy selectively permeable to hydrogen and its isotopes, wherein the tube (T) is set in cantilever fashion with its free end closed, there being further provided elements for applying an axial tensile force on the free end of the permeator tube (T) and elements for electrical connection of the free end of the tube (T) to an end flange (FF) of the module (1) adjacent thereto.